ML20211C133

Summary of 860814 Meeting W/Util,B&W,American Nuclear Insurers & Lrs,Inc in Bethesda,Md Re Detailed Aspects of Action Plan for Performance Improvement at Plant.Viewgraphs Encl

ML20211C133
Person / Time
Site:	Rancho Seco
Issue date:	10/09/1986
From:	Miner S Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
TAC-61631, NUDOCS 8610210276
Download: ML20211C133 (126)

Text

'

a October 9, 1986 Licensee: Sacramento Municipal Utility District Facility: Rancho Seco Nuclear Generating Station

SUMMARY

OF MEETING HELD ON AUGUST 14, 1986 WITH SACPAMENTO MUNICIPAL UTILITY DISTRICT By letter dated July 3, 1986, Sacramento Municipal Utility District (SMUD) submitted its Action Plan for Performance Improverrent at the Rancho Seco Nuclear Generating Station. In a letter dated July 29, 1986, the NRC provided SMUD with general comments on the Action Plan. On August 14, 1986, representatives of SMUD and the NRC staff met in Bethesda, Maryland to discuss the detailed aspects of the Action Plan. Enclosure 1 is a list of meeting attendees. Enclosure 2 is a copy of the material presented by SMUD at the meeting.

SMUD provided an overview of their actions to improve performance at Rancho Seco. They are hiring about 20 people per month and by September will have approximately 1600 people, including contractor personnel, on site. With regard to training programs, 4 have received INP0 accreditation and 6 others have been submitted for accreditation. A new director for Emergency Response has been appointed and they expect to have a full scale emergency response drill completed early in October. The licensee is installing additional holdup tanks for radioactive water to enhance their ability to control liquid radwaste discharges.

The licensee is making systems changes and additions to reduce the probability of transients occurring and to maintain transient effects within predictable limits in the event of plant operational occurrences. To accomplish this objective, the licensee committed to install the EFIC system and have it operational prior to startup. This will isolate the Auxiliary Feedwater (AFW)

System from the ICS. In addition, the controls for Turbine Bypass Valves (TBV) will be modified so that the valves will close on loss of ICS. The licensee is also installing memory modules on the ICS so that the ICS can be repowered after a power loss without causing additional transients. Prior to startup, the licensee will upgrade the SPDS to safety grade and install all Category I Regulatory Guide 1.97 items.

The licensee elaborated on the progress to date on their Performance Improvement Program. About 37 recommendations have been received from the B&W Owners Group (BWOG) program. Six of these recommendations are being implemented prior to restart. None of the BWOG recommendations will impact restart. The failure modes and effects analysis (FMEA) of the ICS was initiated by SMUD on August 7, 1986.

There have been about 340 recommendations from review of precursers, about 1600 recommendations from the plant staff interviews and about 1000 recommendations from the deterministic failure consequences evaluations. The SMUD Recommendations, Review and Resolution Board (PRRB) has processed about 2500 recommendations to date.

The licensee reviewed progres_ on their systems review and test program. The System Engineering function is in place and functioning. To date, 27 systems have been selected for the system review and test program. The remaining 50 l 8610210276 861009 PDR ADOCK 05000312 O pop 1

• t

• 1 f

additional systens are being evaluated to some degree for possible inclusion in the' program (it is likely that, of these 50, an additional 4 will be selected). The licensee will prepare a system status report for each system in the program. Three revisions of the report will be prepared. The first revision (PEV0) will get the system review started. REV1 will identify the testing required and REV2 will provide the results of the test program.

In conclusion, SMUD indicated their current schedule is to start heat-up by the end of January 1987 and be at power about the middle of February (this date has subsequently changed to early May).

Arrangements were made to have follow-up detailed technical working group meetings starting in September.

ORIGl!!AL SIGNED BY Syndey Miner, Project Marager PWR Project Directorate #6 Division of PWR Licensing-B

Enclosures:

As stated gnW PBD-6 PBD PBD-6 6 SMine GKa PWeller JS 10/9/86 10/f/

/ 10/'l /86 10/ ..

gy jn /3 - o/ 6 MEETING SUMPAPY DISTRIBUTION Licensee: SACRAMENTO MUNICIPAL UTILITY DISTRICT

• Copies also sent to those people on service (cc) list for subject plant (s).

(D50cketFilD hRC PUR L PDR PBD-6 Rdg-JStolz SMiner GKalman RWeller OGC-MNBB g604 EJordan BGrimes ACRS-10 NRC Participants JTaylor DHumenansky CYLiang GEdison GPerez JStolz JIsom RCorreia PMilano

- RFerguson PShemanski JCalvo KWichman LBeltracchi -

HGarg RKendall CYCheng GPlumlee, III WPegan

Acappucci RWright CThomas JWenniel SDiab WPaulson DCrutchfield FAllenspach FSchroeder FMiraglia

(

h o . . >r  ;

Enclosure 1 SMUD PANCHO SECO MEETING AUGUST 14, 1986 Name Organization 3fdiieyMiner NRC NRR/PBD-6 Ray Ashley SMUD MANAGER-LICENSING John Ward SMUD DEPUTY GENERAL MANAGER George Coward SPUD PLANT MANAGER James Shelter SMUD NUCLEAR SCHEDULING MANAGER Dan Whitney SMUD ASSISTANT NUCLEAR OPERATIONS PANAGER Jim Taylor .

NRC DIRECT 0P, IE David Humenansky NRC OCM/CHAIPMAN Chu-Yu Liang NRC RSB/DPL-B Gordon Edison NRC NRR/PBD-6 Jim Field SMUD SRTP DIRECTOR Bob Daniels SMUD SUPERVISOR ELECTRICAL ENGINEERING Glen Perez NRC RV RESIDENT INSPECTOR John Stolz NRC NRR/PBD-6 Jim Isom NRC RV BACKUP COORDINATOR Larry Wittrup SMUD 18C ENGINEER Rich Correia NRC/IE VPB Rx ENGINEER Patrick Milano NRC IE/VPB Robert L. Ferguson NRC PWR-B/PBEICSB George Kalman NRC NRR/PBD-6 Rick Weller NRC NRR/PBD-6 Paul Shemanski NRC NRR/PWR-B/PEICSB John Fehringer INEL/NRC CONTRACTOR E. Wayne Roberts INEL/NRC CONTRACTOR Jose A.- Calvo NRC PWR-B/PEICSB K. R. Wichman NRC PWR-B/EB Leo Beltracchi NRC PWR-B/PEICSB Hukam Garg NRC/PWR-B/PEICSB Rick Kendall NRC/DPWRL-B/PEICSB C. Y. Cheng NRC/PWR-B/EB -

G. L. Plumlee, III NRC/PWR-B/F0B William Regan NRC/PWR-B/ FOB A. J. Cappucci NRC/PWR-B/F0B R. J. Wright NRC/PWR-B/EB Cecil Thomas NRC/PWR-B/RSB J. S. Wenniel NRC/PWR-B/PEICSB James Hobin AMERICAN NUCLEAR INSURERS t Sammy Diab NRC/DSR0/RSIB

! Rich Starostecki DEPUTY DIRECTOR /IE Walter Paulson NRC NRR/PWR-B Dennis Crutchfield NRC NRR/PWR-B Lester Berkowitz W/NTSD l Fred R. Allenspach NRC NRR/PWR-B l Jacque Lingenfecter SMUD SYSTEM REVIEW & TEST PROGRAM John Bohart MANAGER ENGINEER SUC/B&W Bill Wilson I&C ENGINEERING /B&W l

l

5 e

} , ? - r

_2 Name Organization Ed Kane MANAGER NUCLEAR ENGINEER /B&W Bud Beebe SMUD 18C (EFIC COG.)

Dave Seavers AMERICAN NUCLEAR INSURERS J. H. Taylor BABC0CK & WILCOX R. C. DeYoung LRS INC. (CONSULTANT TO SMUD)

Frank Schroeder NRC NRR/PWR-B Frank Miraglia NRC NRR/PWR-B

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\ MEETING WITH NRC TO DISCUSS i RANCHO SECO ACTION PLAN i August 14, 1986 l

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Purpose:

l

• To present details concerning Action Plan progress.

l e To obtain sense of staff regarding System Review &

l Test Program and certain physical plant modifications.

l Scope:

e Performance improvemnt Program 1

e System Review & Test Program l

l

• Instrumentation & Control items

( -ICS/NNI l -Auxillary Feedwater System l -Auto initiation of AFW System e Schedules

• B&W Owners Group Interface

\ e Reports, Amendments and Information Submittals ,

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i II. INSTRUMENTA TION AND CONTROL ITEMS I

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4 SYSTEMS IMPORTANT TO .

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SECONDARY SIDE l HEAT REMOVAL i

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MAJOR CONTROL SYSTEMS

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SAFETY PARAMETER DISPLAY SYSTEM (SPDS) .

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BAILEY COMPUTER BALANCE OF cPLANT (BOP) INSTRUMENTATIDN I

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• BLOWN FUSE I

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SUPPLY FAILURE l ANALYSIS -

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i l WITH PLANNED MODIFICATION INSTALLED l CONTROL & INDICATION OF SECONDARY SIDE HEAT REMOVAL CAPABILITY EXISTS WITH l ANALYZED POWER FAILURE MODE I

l 1 _ _. __ ________ _ __ _____ _ ___ _ _ _ _ _

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MAJOR ICS/NNI MODIFICATIONS l FAIL CLOSE TBV ON LOSS OF ICS

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• INCREASE CAPACITY OF DC POWER SUPPLY s

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• LABEL S1 & S2 SWITCHES

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CABINET FAN FAILURE l

DC POWER SUPPLY FAILURE

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l POWER SUPPLY MONITOR (PSM) .

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• THE PSM DID NOT MALFUNCTION OR FAIL ON 12/26/85 i

• THE PSM WORKED CORRECTLY AND AS DESIGNED I

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• THE PSM SHOULD HAVE TRIPPED THE ICS i

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i ICS/NNI INTERACTION .,

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i WITH SAFETY SYSTEMS -

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ICS/NNI FAILURES CANNOT PREVENT OPERATION OF SFAS .

'AF N RPS .

4 EFIC i

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NONE OF THEiE SYSTEMS RELY ON 3CS INPUTS OR POWER SUPPLIES TO ACCOMPLISH THEIR SAFETY FUNCTION

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- 1 i CONCLUSION -

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SAFE CONTROL AND INDICATION I =

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LOSS OF MFW (ANTICIPATORY REACTOR TRIP) l MANUAL

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STARTS AFW PUMPS l ACTIVATES CONTROLS

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AFW SYSTEM INDEPENDENT OF ICS 1

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4 CHANNEL SAFETY GRADE ,

INITIATION SYSTEM

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• MAIN STEAM LINE LOGIC SYSTEM INDEPENDENT OF ICS ,

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• CLASS I MOV USED TD' ISOLATE MFW ON A MAIN STEAM.LINE BREAK.

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• CLASS I INSTRUMENT AIR PROVIDED TO i CLOSE MAIN AND SU VALVES ON MSLF l e l

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MANUAL CONTROL AT SHUTDOWN, PANEL AUTOMATIC CONTROL IN CONTROL ROOM POSITION INDICATION .IN CONTROL ROOM o TBV'S o

GO FULLY CLOSEb ON LOSS OF ICS POWER a

THE FOLLOWING- CONTROLS AND INDICATIONS ARE INDEPENDENT OF ICS POWER MANUAL CONTROL IN CONTROL ROOM MANUAL CONTROL AT SHUTDOWN PANEL _

I POSITION INDICATION IN CONTROL R.00M o

AUXILIARY STEAM PRESSURE CONTROL VALVE

• CONTROL INDEPENDENT OF ICS POWER t

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_ _ _ _ ___ _ _. - - - - - - - - - - - - - - - - ~ -~

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OTSG OVEllFILL PROTECTION .

EFIC PROVIDES :

• OTSG AUTOMATIC LEVEL CONTROL (AFW)

• MFW ISOLATION i

• OTSG HIGH LEVEL ALARM G

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l *OTSG PRESS

• PRESS LEVEL l =-CLASS 2

• ETC.

- CLASS I't j ~

g EllC RPS CONTROL g

a aPRESS IlEATERS e PHESS LEVEL l l '

11 11 eETC.

SIGNAL ISOLATION igTp k CONVERSION  : J ICS CABINETS CABINETS (B) (0) 1

= INDICATION INST. INPUT- g MULTIPLEXER = SPDS e FW FLOW e HZ (8) ,_ (B) -

• NEUTRON ERROR CONTROL

• MFW PUMPS

• MFW VALVES ICS/NNI SPDS . rev CON ~~ROL INDICATION *'*

'~~

SAFETY PARAMETER DISPLAY SYSTEM R.G.1.97 INSTR UM ENTATION

• SPDS CLASS 1E DlESEL BACKED REDUNDENT POWER

• SPDS POWER IS INDEPENDENT OF ICS/NNI

!

• HOT SHUTDOWN INSTRUMENTAT10N INDEPENDENT OF ICS/NNI !

• CATEGORY I RG.1.97 INSTRUMENTATION - REDUNDANT

INDEPENDENT OF ICS/NNI i

• OTSG LEVEL WITH :: 2% OF OTHER OTSG LEVEL INDICATION IN CONTROL ROOM

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SECONDARY SIDE HEAT REMOVAL IS POSSIBLE THRU

• CONTROL SYSTEMS i

PROCESS SYSTEMS'

• INDICATION SYSTEMS i

j j SUPPORT SYSTEMS NOW DESIGNED AND ADDRESSES RELATED CONCERNS

RAISED IN NUREG 1195 9

~ " " " * * - . .- . . m..._ ,

e t_

O l

i 9

Ill. PERFORMANCE IMPROVEMENT PROGRAM

& BWOG INTERFA CE

( 142C l PERFORMANCE IMPROVEMENT PROGRAM OUALIT Y/A GN

- ACTION PLAN -

REPORT

~

~

CLOSEOUT TO RIN l

I l

APPROVE SYSTEN STATUS REPORT PERFORMANCE PERFORMANCE A NAL YSIS GROUP

• ANALYSIS GROUP

• di II l

TEST l I

REVIE W RESPONSIBLE W IV'!.EMENTING w IMPLEMENTihG ~ w SYSTEN ICPLEMENTING OUALITY m GROUP w ENGINEER GROUP GROUP

• 16 il JL di it SCHEDULING S CHEDULING .-

Disposition by

1. • U*'***** - f**# ****

Intelld  : ~

Analysis Group " to RRMB h di Sche duling =

Input From _

~

System $ y TESTMODS Dept. Mgrs. -

Review (~& MAINT ~

FSARj Management .

Recommendations Process Review & Resolution Group Board b

De terministic Plant Staff Fallute Consequences Interviews BWOG Stop-Trip Selected '

Projects Prodrom

\

12/26/8S Event & p ,,,

NUREG 1196 g,,,,,

Action List o INCLUDES DGM, NUCLEAR CONCURRENCE

I ~ -

J i,

~

(1446 )

Relationship of PP & MIP to SRTP

• PP & MIP Provides Systematic Inputs to SRTP 1

e PP & MIP Provides Prioritization and Disposition of l

l non-System Items l

• SRTP Provides Comprehensive Assessment of System i Relevant Items l

\ ACTION PLAN NUREG 1195 FINDINGS e All 26 Findings Addressed in Appendix B l

i e Status and Results Provided in July Submittal

! e Will Amend as new information is developed in PP & MIP e

l

~

'. i~

' ' ~ '

PP & MIP -

. PROGRESS TO DA TE Investigations ,

1 12/26 Event Action List

-150 Analysis ~, Investigations, Studies, Modifications, Reports

-34 Remain Open '

l -These items generated 400 Recommendations l -Recommendations input to 001-12 Process ,

i

! Major Investlaations

-ICS Performance

-RCS Response and Effects of Cooldown Transient

-Human Factors

-MU Pump Failure

-Health Physics

-Emergency Plan

-Training

-Operailonal Assessment

-Procedures Action Plan Elements

-Upgrade Operating Procedures per 12/26 Assessment

• Procedures' Generation Package

• V & V of EOP's

-ICS Mods *

-Upgrades Address Every Investigation Area i

t

( 1487 )

PP & MIP PROGRESS TO DA TE i investigations BWOG Safety And Performance Improvement Program (SPIP)

(Previously The "STOP-TRIP" Program) l e 3 7 Trlp Reduction Recommendations Recevied l

• All Processed Per 0C1-12 l e Disposition:

-Implement, Prior to Startup, 6 -N/A, 6

-Implement, Near Term, 6 -Already Covered, 5

-Implement, Long Term, 5 -Living Schedule, 8

-DFC Analysis,1 BWOG/SMUD Interface

-SMUD Respresentatives on Task _ Forces, Committees

-Expect another 100 Recommendations thru End of Program

-No Items deterred to BWOG which are Required for Restart

-No Unreviewed Safety Questions l

l i

l

l .

~. i' cmm BWOG SPIP l

Recommendations To Date l

Prior To Startup

• Improve Reactor Runback Capability

e improvements in ICS Tuning Control Circults ,

i e Determine if Grid Frequency Error Circuit has been

Detuned

! e Adequacy of Operator Aids to detect Loss of NNI I

l e Determine Need to Replace MSSV Release Nut

] Cotter Pins I e Calibration Techniques for Power Range imbalance Affected Systems:'

-lCS, 16

-Main Feedwater, 7 -Reactor Protection System,1

-Auxillary Feedwater,1 -Op s, 1

-Maln Steam System, 2 -A dmin, 5

}

-Maln Turbine System, 2 -N/A, 2 I

j i

j -

t

. ( I4441 -

PP & MIP PROGRESS TO DA TE Investigations

- Precursor Review l e Documents Reviewed

-212 TAP Reports

-Rancho Seco Documents l -Trip Reports

-L ER 's, O D R 's

-Operational Assessments Root Cause. Reports i -INPO SOER's

-NRC

-NUREG 's

-lE. Bulletins

-Circulars, Notices

-Generic Letters l ~B & W

-PS C 's

-Site Instructions

-Relevant BA W Reports

-Service Bulletins

• Status

-340 Recommendations to Date

-Expect 400 Recommendations Total

-Finish Review 8/18/86

~ 1350 Documents Reviewed _

t . . -

4 cTTrn

, PP & MIP PROGRESS TO DA TE ,

Investigations e Plant Staff Interviews 180 Volunteer Interviewees

- Represented AII Functions On-Site

- Broad Cross-Section l - Background And Training Of Interviewers

- Interview Methodology

- Over 1631 Recommendations (19 Anonymous)

- Human Factors And Operational Issues

- Feedback Results '

e Inter.vlow Format

- Anonymous, If Requested

- Structure, One-On-One, Or Group (As Desired)

- Form: Specifically addressed systems

- RCS, ICS, Electrical Distribution, Reactor Auxiliarles, Secondary Systems,

! Plant Support Systems

- Used Prepared Questionnaires

- Focus On:

- Plant Safety / Reliability

- Problem / Concern / Consequences

- Recommended Solution i

(

MINIMUM NUMBER OF PERSONNEL TO BE INTERVIEWED i

Opera tors 24 . \

Tech Support, Engineers & STA 's 7 i Sche duling 2 l Plant Maintenance 35 Security 4 NPS (Labor) 20 Licensing 4 Training Instructors 10 Nuclear Engineering 29 Quality 9 Rad Protection 7 Chemistry 6 TO TA L 15 7 f

1 (I478)

FINDINGS FROM INTERVIEW PROCESS a Control Room Pushbuttons are falling due to Age and Use e Design of Site Metrological System Effects its Reliability e Rollef Valves on Diesel Generator Air Receivers have History of Weeping / Leaking e Hotwell Reject Valve has History of Falling Open l

• MFW Block Valve Travels Full Stroke Before Reversing 1

e Aux Boller Operability / Safety 1

e EHC Trip of Turbine / Reactor on Transfer l

l l

1

~

1,

( I4tB )

PP & MIP PROGRESS TO DA TE In vestigations

Deterministic Failure Consequences e Addressed

-Loss of Electrical Power

-Loss of lirstrument Air

-Loss of ICS/NNI e Analysis Complete on:

-All Electrical Buses

-Instrument Air

-ICS/NNI e Analysis Remaining:

-Fallure of Startup Transformers

-Loss of Offsite Power

-IE Bulletin 79-2 7 " Loss of Non-Class 1E Instrument i and Control Power System Bus During Operation" e Effort:

-Approximately 20 Engineers, Technicians, Operators

-11 Week Task e Results:

-Approximately 1,000 Recommendations

-Expect 20% To- Be Redundant At RRRB

-550 Recommendations To RRRB To Date

-Scheduled Completion, 8/18/86

-Validated ICS Reliability Analysis, BA W-1564 For Rancho Seco

t #4e9 )

EXAMPLES OF DFC FINDINGS e Loss of Power to Instrument Air Dryers Vents to Atmosphere e Momentary Interruption of Power to EHC on Auto Transfer Trips Turbine / Reactor e Control Room Test Panel has unbuffered inputs e All RCP CW Lo-Flow alarms have common power, single failure leads to Inadvertant RCP shutdown, Natural Circulation e Loss of "E" Battery prevents transfer of Loads from Auxillary to Startup Transformers. Natural Circulation Results e Need for Annunciator Reflash capability to improve plant reliabillty

• USAR describes Circ Water Discharge Valves as Pneumatic Operated, they are Hydraulic Operated e" Plug strip" powered from vitai Inves ter. Inadvertant use could fault power supply to CRD Logic aind NNI e Need for specific procedure and dra wing changes e Loss of power to primary Turbine Tilp defeats the Manual Control Room Trip Button e MFW Pump A & B Governor Valves are powered through a single fuse e

l l

i l

{ 1447 )

l PP & MIP PROGRESS TO DA TE Recommendations. Review, and Resolution Board (RRRB) '

• Meets Daily e Has Received and Processed ~ 2,500 Recommendations

• Expect 3,000 Recommendations to be Submitted e Recommendations Apply to 69 systems l

l e 1,500 Consolidated Recommendations being Tracked l

e 839 Valid Recommendations being Resolved

/ ,

~

ee-I e- .u 1; e;. .

I. . j

i

~

~ ..

,~. ..

...-yg ,

W p- ~.A l ". - -4,

.. MUD-NRC MEETING Qj dF g :a:a[,; j -hs. 3 l . -

t .n, '... .a~- -

-- _. mag

. : ~ , , n~ ~,> .

l --

RANCHO SECO AUGUST 4My a Ih8h nuclear generating station Bookif

• \ -

f

, _ _ , = _

1 s

l I

I 1

i e

IV. SYSTEM REVIEW & TEST PROGRAM 6

1 e.

- k o a. . . . . . , ,

~

C 1423 )

SYSTEM SELECTION 2 Catagories Of Systems

• Selected Systems

• Additional Systems Both are being investigated to some degree.

i i

• I

( 1424 3 SNLECTED SYSTEMS Quantity: 2 7 as of 8/14/86 Criteria:

1. History of significant or recurring problems.

l 2. Related to the 12/26/85 Event.

l i

l 3. Is being significantly modified.

4. Has significant potential for Initiating or adversely affecting transients.

I *

(I427 ) -

i i

)

I

, SELECTED SYSTEMS Reactor Plant

• Reactor Coolant System

• Decay Heat Removat System l

• High Pressure Infection System l

• Seal injection And Makeup System l

• Purification And Letdown System l

• Nuclear Service Cooling Water System i

• Nuclear Service ~ Raw Water System l

l 1

l

(1428 )

i SEl.EC TED S YS TEMS Steam Plant

• Staam Generator System

• Main Steam System

• Main Feedwater System i

• Auxiliary Feedwater System

?

I -

l -

t Ls2J i

i l SELECTED SYSTEMS Power And Control e Reactor Protection System (including ARTS)

• Safety Features Actuation System

• Main Steam Line Failure Logic System o Integrated Control System e Non-Nuclear Instrumentation System

• 125 Volt DC Vital Power System

• 125 Volt DC Non-Vital Power System e 120 Volt AC Vital Power System

• 480 Volt AC System e 4160 Volt AC System

• 6900 Volt AC System I *

( I430 )

SELECTED SYSTEMS

'l A uxiliary

) .

e Control Room /TSC Essential HVAC System o Emergency Diesel Generator System (including Fuel Oll)

• Component Cooling Water System

• Plant Air System o Instrument Air System

~1 -

(_1431 3 ,

ADDITIONAL S YSTEMS Quantity: 50 as of 8/14/86 Criteria: 1. The 0C1-12 input phase has identified a problem with the system.

i

2. An open Work Request existed against that system as o f 7/1/8 6.

, (1425)

ADDITIONAL SYSTEMS Reactor Plant l

l

• Borated Water System

• Core Flood System i

j

• Containment Building Spray System l

• Control Rod Drive System

• Pressurizer Relief Tank System

• Spent Fuel Cooling System

• Reactor Coolant Drain System I

'l -

l

~

I

e f14267 I

ADDITIONAL SYSTEMS Steam Plant

• Air Elector System 1

l

• Extraction Steam System

• Gland Steam And Condenser System I

l

• Heater Drains And Vents System

• High Pressure Turbine System

• Low Pressure Turbine System o Main Condensate And Makeup System l

l l

't

- - ^

( ,,3,3 ,

~

A DDITIONA L S YS TEMS.

1 l

Power And Control

• Annuciator System l '

l

• Cathodic Protection S'ystem l

• Plant Communications System

• Electro-hydraulic Control System l

• Main Generator System i

l

• Nuclear Instrumentation System l

• Plant Computer System 1

• Plant Security System -

• Radiation Monitoring Systent

• Seismic Monitoring System l

• Turbine Supervisory Instruments 1

( i432)

ADDITIONAL SYSTEMS Auxiliary

• Auxillary Steam System

• Drainage And Sewage System

• Cranes And Holsts

• Carbon Dioxide System

\

• Diesel Fuel Oil System i

• Demineralized Water System

• Fuel Handling System

'

• Fire Protection Water System

• Hydrogen Gas System i

• HVA C - Other

• Lube Oil System

• Main Circulating Water System j

• Nitrogen Gas System I

1 maza l

ADDITIONAL SYSTEMS

~

'l Auxiliary Cont.

• NSEB Essential HVA C j

• Plant Buildings And Structures j

• Plant Cooling Water System l

• Reactor Sampling System

• Radwaste System

• Secondary Chemical Addition System i

)

• Seal Oil System

• Site Reservoir System

• Service Water System

• Turbine Plant Cooling Water System

• Turbine Plant Sampling System

• Waste Gas System

) -

l l

SYSTEM REVIEWS AND REPORTIN,G t ,m >

O CI- 12 Input Process l

Valldity Data Base RRRB Priority Sort Systems Related Management Issues Additional Systems l Selected Systems t t Rev 0-SIR

• 4 = SSR - Rev 0 t i System Engr Inlllates Work Kick-off Meeting t t Rev I-SIR M = = SSR-Rev 1 = =

L Test Spec  : TRG

~* Test

_ Procedures 2 =

Test Results  :

i f

= = SSR - Rev 2 l t

= Restart Decision i -

l

e ( 1439 ) ,

SELECTED SYSTEMS REV 0 SYSTEM STA TUS REPORT l

l l

Purpose:

Get Plant Work Started Content: System Functional Description (Summary)

Executive Summary -

l Problem Statements l Open Work Request Review l

Reviewed By: Performance Analysis Group I Deputy General Manager, Nuclear i

j .

( I434 )

l SELECTED SYSTEMS l REV 1 SYSTEM STA TUS REPORT I

Purpose:

Identify Testing Content: Rev0 l System Functional Descri.etion (Detailed) l Test Identification i Open ECN Review Additional Problem Statements I

Reviewed By: Test Review Group

! Performance Analysis Group Deputy General Manager, Nuclear I

i

! O l

l

\

a

~I

( 1448 7 SELECTED SYSTEMS TEST SPECIFICA TION ~

Purpose:

Detail Specific Test Content: Purpose Test Method Acceptance Criteria l

Reviewed By: Test Review Group l -

l -

i q

I

( 1435 )

SELECTED SYSTEMS i

REV 2 S YSTEM STA TUS REPORT

Purpose:

Final System Acceptance -

i Content: Rev 1 l System Walkdown

! Maintenance History Trends Test Results To Date l Comparison To Davis Besse l Operability Finding

+

Reviewed By: Test Review Group Performance Analysis Group Deputy General Manager, Nuclear i ,

] .

i i

i .

.( 1449 )

SELECTED SYSTEMS 1

SYSTEM FUNCTIONAL DESCRIPTION i

i Source Documents:

1' e NEP 5400 (SMUD System Design Bases) e Updated Safety. Analysis Report e Rancho Seco Technical Specifications jj .* B&W Guide Specifications j e Rancho Seco Design Manual (Bechtel)

• Design Calculations (As Applicable) e Vendor Manuals Documentation:

• Rev 1 & Rev 2 of System Status Report Re vie w:

• System Design Engineer e Test Review Group e Performance Analysis Group

• Deputy General Manager, Nuclear l

~

l -

l [ e 450 )

l TEST IDENTIFICA TION setecreo sysrents l

l Process: -

For each system' function ident! fled the System Engineer will e Identify existing test procedures which adequately demonstrate the function to be conducted prior to re s tart, e Identify new test requirements to demonstrate the function prior to restart

OR l

• Prepare a justification for not testing the function l prior to restart ,

j Documentation:

l '* Rev 1 & Rev 2 of the System Status Report i

i Re vie w:

! e Test Review Group

\ e Performance Analysis Group

• Deputy General Manager, Nuclear l

l i

(_l452 )

SELECTED SYSTEMS ADDITIONAL SYSTEMS 1

i PROBLEM STA TEMENT FORMA T I

\

• Problem:

I l * . Tracking Number:

i -

• Priority:

i i

• Source:

l

• Descrip tion:

l i

• In vestiga tion:

lI l

• Resolution:

4 l

• Testing:

l

l. .

1

~

i l

I456 7 i

OPEN WORK REQUEST REVIEW SELECTED SYS.TEMS ADDITIONAL SYSTEMS l

Scope: All Open Work Requests as of July 1, 1986 l

l Criteria: The work must be performed If:

l e Make the system OPERABLE per ,.

l Technical Specifications.

l

• Satisfy an external legal commitment.

e To operate in accordance with

! approved procedures.

e Eliminate a personnel hazard.

l' .

o Prevent significant deterioration of

) affected system or other plant equipment.

1 l

• Result in an appreciable reduction in

contamination or Ilquld radwaste.

l e Eliminate an inope'rable control board

\ annunciator, Indication or control.

1 Documentation: Problem Statement Format Re vie w: Performance Analysis Group 4

Deputy General Manager, Nu' clear i i .

~

j - ,

i 8

4

( 1457)

OPEN ENGINEERING '

! CHANGE NOTICES (ECN's) REVIEW SELECTED SYSTEMS ADDITIONAL SYSTEMS Criteria: Priority 1 - Restart l

• Assure plant remains in Post-Trip Window

• Assure compliance with Technical Specifications -

• Minimize the need for Operator action outside i the Control Room within the first ten minutes l of an event l Priorsty 2 - Near Term l

• Enhance ability to remain in Post-Tip Window

• Reduce reactor trips s

Reduce challenges to Safety Systems l

• Produce Near-Term Programmatic Benefits Priority 3 - Lonus Term

• Improve reliability

}

• Improve availability

• Major Programmatic enhancements Do cumentation: Rev 1 & Rev 2 System Status Report Rev 0 & Rev 1 System Investigation Report

Re vie w

Performance Analysis Group

{ Deputy General Manager, Nuclear i .

i

( 1451 )

SELECTED SYSTEMS SYSTEM WALKDOWN Criteria:

• A Checklist will be developed to assure consistently thorough Walkdowns.

1

- Material condition of equipment

- Undocumented temporary mods

- Calibration of instrumentation

- ETC e Performed by System Engineer and Operator Documentation:

• Rev 2 System Status Report Re vie w:

• Performance Analysis Group e Deputy General Manager, Nuclear I -

l i -

t

{ 1455 )

SELECTED SYSTEMS RECENT MAINTENANCE HISTORY REVIEW '

MAINTENANCE HISTORY TREND REVIEW

! i i

Process:

I

• All Maintenance from 12/26/85 - present will be reviewed for adequacy of Post l

\

Maintenance Testing.

\

\ e Trends of maintenance history will be created and, lowed for recurring problems.

Documentation:

• Rev 2 System Status Report i

l Re vie w:

\

• Performance Analysis Group

• Deputy General Manager, Nuclear 4

i

• 1 i

W5B 1 SELECTED SYSTEMS i

REVIEW OF DA VIS-BESSE RESUL TS I

Criteria: The System Problem and Test Review Reports from the Davis-Besse SRTP will be reviewed for applicability to the corresponding

l. Rancho Seco system.

l Documentation: Rev 2 System Status Reports

Re vie w: Performance Analysis Group Deputy General Manager, Nuclear -

i i

l i -

l

I 8

1

( 1479 )

FINAL SYSTEM STA TUS REPORT i

SELECTED SYSTEMS i

CONTENT i e Executive Summary e System Functional Description e Problem Statements e Test Review 1

• Open Work Request Review

e Open ECN Review i i i

! e System Walkdown e Maintenance History Trends l

i e Test Results  :

e Davis-Besse Comparison *

• Operability Finding  ;

1 4

~

I t

[ 1483 )

Problem (14): NNI-Y Negative 24 VDC power supply does not meet manufacturer's specifications for AC ripple and noise.

\ Tracking Number: 26.0077 I

t i Priority: 1 Source: WR# 113849 (6/25/86)

Description:

NNI-Y Negative 24 VDC power supply does not meet I manufacturer's specification for AC ripple and noise.

l This could possibly cause the power supply not to

perform as required.

investigation:' Review of open work requests - WR# 113849 (6/25/86) l The engineering requirements for this work request are to l rework and recalibrate this power supply.

Resolution: l&C maintenance will complete WR4 113849 l

\ Testing: Later I

i -

2

SYSTEM PROBLEM The "hardcast" tape used to seal the Essential Air Handling Units against air infiltration has not been documented as being c,ualified for long term exposure to expected environmental conditions.

TRACKING NUMBER: 26.0150 .

PRIORITY: 1 SOURCE: System Design Engineer DESCRIPTION During the startup testing of the Essential HVAC System, it was revealed that the air handling units could not meet the leakage criteria of ANSI N509-1980 due to inadequate design and fabrication of the unit housing. - Hardcast" tape was used to seal all of the joints of the housing based on assurance of qualification from the manufacturer of the tape. Upon evaluation of the qualification information available, it was determined that there was insufficient data available to establish a qualified life of the tape.

INVESTIGATION Becht'el has attempted to provide a qualification for the tape based on the limited available information from the manufacturer of the tape, however, has been unable to provide a cualified life of the material due to the proprietary nature of the components of the tape.

RESOLUTION OF PROBLEM Prior to restart, a procedure will be developed for periodic inspection of the tape application on the air handlers to verify that the integrity of the housing has been maintained. The inspection will be performed in conjunction with other testing to be performed on the units as a result of other modifications.

~

• ' For the short term, the tape shall be submitted for environmental qualification. to determine the expected life of the material.

TESTING A housing -leak test which will be performed following ' modifications to the air handler access doors (Ref: Tracking Number 26.0002) will also verify the integrity of the taped joints of the unit.

4-31 m

8 v

t (I437 )

ADDITIONAL SYSTEMS REV 0 SYSTEM INVESTIGATION REPORT l

l Purp ose: Get Plant Work Started Consider For " Select" Status Content: System Functional Description (Summary)

! Executive Summary l Problem Statements l Open Work Request Review Open ECN Review Reviewed By: Performance Analysis Group l Deputy General Manager, Nuclear i

i t

i ) -

I

~

j ( 1438 )

i ADDITIONAL SYSTEMS REV 1 SYSTEM INVESTIGA TION REPORT

\

Purpose:

Final System Acceptance l Consider For " Select" Status

Content

Rev0 +

l Additional Problem Statements

. Operability Finding l Reviewed By: Performance Analysis Group Deputy General Manager, Nuclear

l -

l (1455)

ADDITIONAL SYSTEMS UPGRADING TO " SELECTED" STA TUS Criteria:

i

• Significance of Identified Problems

-o r-l j

• Quantity of Indentitled Problems l

Process:

• System Engineer Asakes recommendation In 5ystem Investigation Report.

• Performance Analysis Group makes -

final decision.

5

.1 -

[ 1480 )

FINAL SYSTEM INVESTIGA TION REPORT ADDITIONAL SYSTEMS CONTENT .

• Executive Summary

• System Functional Description ,

Problem Statements

• Open Wo'rk Request Review e Open ECN Review e Operability Finding r

O SYSTEM REVIEWS AND REPORTING n em >

Q CI- 12 loput Process .

Validity Priority Data Base RRRB Sort Systems Related Management issues Addllional Systems l Selected Systems

, t t Rev 0-SIR M & SSR - Rev 0 l t t

System Engr Kick-off Meeting initiates Work ~

, t t Rev I-SIR M = = SSR - Rev 1 = =

1 '

l L Test Spec - -

TRG

~

PAG

+ Test

_ Proc edures 2 =

Test Results ;

l . . .

I I

l

= = SSR Rev 2 I

t

" Restart Decision i .

i -

l j .

I i N SYSTEM REVIEW AND TEST PROGRAM j RANCHO SECO / DA VIS-BESSE COMPARISON l

l System Selection l

Rancho Seco .

Da vis-Besse

e Selection criteria includes e Selection criteria includes

! non-safety systems non-safety systems i e 2 7 systems Initially selected e 31 systems initially selected i

e Process for inclusion of ad- e During course of program ditional systems established - 3 additional systems in-

- 4 probable system addition *cluded in program identified to date '

e Partial system reviews to be e Systems outside program performed on all remaining deferred for subsequent' systems with any identified re vie w.

problem or outstanding l Maintenance Work Orders.

i l

I l

1 1

i 1

i

~

i l

~

f e4t4 )

SYSTEM REVIEW AND TEST PROGRAM

RANCHO SECO / DA VIS-BESSE COMPARISON Problem Identification i Rancho Seco Davis-Besse ,

j

• System based problem identification e System based problem Identification

- Review of outstanding work orders - Review of outstanding work orders l

- Review of open ECN's - Review of open FCR's(ECN's)

- Review of mnIntenance history trends - Review of maintenance history trends ,

- System walkdown for material - System walkdown for material condition conditlen l

- Input from day-to-day system - Input from day-to-day system responsibility responsibility

- Review of test results of comparable .

Davls-Besse system

- Review of Licensee Event Reports I - Review of significant DCRDR - Review of significant DCRDR Human Engineering Discrepancy Numan Engineering Discrepancy Reports Reports

- Review of Transient Assessment Reports

- Input from Operations and Maintenance personnel

{

t

• Programmatic based problem Identification l Includes:

\

- Precursor review

- Plant staff Interview l

- Deterministic failure consequences

- B& WOG Stop-Trip Program

- Other PP & MIP activities

) .

( e4 s )

SYSTEM REVIEW AND TEST PROGRAM RANCHO SECO / DA VIS-BESSE COMPARISON System Review ,.

Rancho Seco Davls-Besse e System level functions to be e System level functions to. be Identitled for each system 'i dentified for each system t e Problem identification both

• Problem identification syste_m and programmatically system based based e Problem prioritization criteria e Problem prioritization criteria ,

procedurally estabilshed procedurally established  :

• Corrective actions developed e Corrective action developed and recommended by System by System Engineers Engineers and PP & MIP

• Problem report review and

• Problem report review and corrective action concurrence corrective action concurrence by PA G by IPRC ,

i i

~

I

~'

l . '.-

( e4:2 ) l f

t i

i SYSTEM REVIEW AND TEST PROGRAM l RANCHO SECO / DA VIS-BESSE COMPARISON i

Test Program Development Rancho Seco Da vis-Besse l

• Identify new test requirements e Identify new test requirements for functions not adequately for functions not adequately

, tested tested

) i 1

• Identify retest requirements e identify retest requirements

! for functions previously tested for functions previously tested '

I or provide justification for or provide justification for why retest not required why retest not required

• Identify new test requirements

• Identify new test requirements to support plant modifications to support plant modifications l .

l

• Review and approval of test e Review and approval of test

{ requirements by TRG and PAG l requirements by IPRC t

I

) .

l l

~

c i4:3)

SYSTEM REVIEW AND TEST PROGRAM RANCHO SECO / DAIVS-BESSE COMPARISON Restart Testing Rancho Seco Da vls-Besse Test specifications and test Test specifications and test procedures to be prepared procedures to be prepared under existing procedural under existing procedural controls controls -

Test specifications and test Test specifications and test procedures to be reviewed procedures to be reviewed by TRG by JTG Test leaders to be tralned Test leaders to be tralned and quellfled on station and quellfled on station testing program requirements testing program requirements All test results required to AII test results required to verify function to be reviewed verify function to be reviewed by TRG by JTG & IPRC I -

O 8 I'

REVISED 12 AUGUST 86 RESTART i IM P LEM E N TATIO N M g gER i I  !  !,

l, SYSTEM REVIEW TF:ST AND TEST RE /IEW PROGRAM DIRECTOR GROUP JIM FIELD PROCESS AND TEST PROGRAM IKM C!t.13eo l 5 STEN PROGRAM REVIEW' DOCUMENTATION ASSISTANT MICH LENTZ ASST. DIRECTOR' ASST. DIRECTOR' DIRECTOR .ERRY BAfBER

, I ' NIKE CLARK JACQUE. I JACK '

STEVE VINCE PRITCETT LINCENFELTER JANUS '

PICCOLO (VACANT)

' TNG SECRETARY,(VACANT) i l l l l l l l "'#E u",# 'T"rg"uY' ,,,,T& 'ME AIM WODigflON SURVEIL &.ANCE EMS R EMG A SSN Speepegga SUPERvisOn SPECIAusf L.PR$TCHETT G. PAPTZLM 8. l'RASEF. 8. CDM$LIN J. RACMLEY R. lCDTE N. THINEAUX t

I. ,

l f

l SYSTEM j SYSTEM SYSTEMS START-UP l SYSTEM ll SYSTEM t suRvCH. LANCE ,

ENGINEERS f ENGINEERS l l ENGINEERS ENGINEERS , ENGINEERS j ENGINEERS l SCHEhWLER J. TutRET [. FREEKM L. WITimF G. ARON C. KELSEV R. COTE M. UlGN T. FAVOLE J. KIE P. WACER D. CLARK L. ALWAfGT A. LOCY K. PolELL B. BAROTT J. BALDAAF S. BADER J. E WEY D. BRVDEN J. WITTE T. LOVETT M. REALE 8. THEMAS W. IEST R. OEEDS K. DAVIS J. DELRUE R. Lise D. SWIDA D. GEKR D. BLAOGETTER

5. EVANS J. DetX J. IO GRICKS C. MDWAfm L. ALVDRADD

5. 54tMAE!

C. PtFPELL R. DEL IMSARIO T. VEALE i

1 (I440 ) ,

j i  !

~

Output .

I l

\ System Status Reports Rev0 i Rev 1

)

1 Rev 2 i

2 I I

Test Specifications Test Procedures i

System Investigation Reports Rev0 i

Rev 1 i

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)

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( e475 )

SELECTED SYSTEMS Reactor Plant new a new s Approved Approved by PAG by PAG Reactor Coolant System 8/20/86 9/17/86 .

Decay Heat Removal System 8/18/88 9/15/86 i

-Hl9h Pressure Injection System 8/27/86 9/24/86 Seal Inject;on and Makeup System 8/28/86 9/25/86 Purification and Letdown System 9/10/86 10/8/86 Nuclear Service Cooling Water System 8/22/86 9/19/86 Nuclear Service Raw Water System 8/11/86 9/8/86 i

i l

i 1

• O

a -_ . .m ..- -# - 4 . - . _ _ - - +-- u -.- - wa. - -== w-. _ - - ,i.i.---.- A-,-- - - m - , _ h- 4 - - . --.u -.- -_-.__. -- - m.--- A.+

l .

[ e4 74 3 SELECTED SYSTEMS Steam Plant i new a new s Appro ved Appro ved  !

l

\

by PAG by PAG I

i Steam Generator System 8/30/86 9/27/86 l Main Steam System 8/14/86 9/11/86 I

Main Feedwater System 8/13/86 9/10/86 l

Auxiliary Feedwater System 8/13/86 9/10/86 i

i I

l i

1 l .

4

)

1 N

SELECTED SYSTEMS Rev 0 Rev 1 Power ControI ' "'*'** ^*'*'**

by PAG byPAG Reactor Protection System (Including ARTS) 8/25/86 9/22/86 i

!

• Safety Features Actuation System 8/15/86 10/15/86 Main Steam Line Fallure Logic System 8/12/86 10/8/86

• Integrated Control System l 7/21/86 8/21/86 i

• Non-Nuclear Instrumentation System 8/5/86 9/11/86 i

• 125 Volt DC Vital Power System

) 8/16/86 9/27/86 125 Volt DC Non-Vital Power System 8/30/86 10/11/86 1

• 120 Volt A C Vital Power System 8/28/86 10/8/86

• 480 Volt AC System l 8/27/86 9/24/86

• 4160 Volt AC System 9/17/86 10/22/86

• 6900 Volt AC System 9/10/86 10/8/86 1 -

O

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}

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! SELECTED SYSTEMS I

1l Rev 0 Rev 1 l

A uxiliary Approved Approved sr raa sr raa

!'

• Control Room /TSC Essential HVAC System 7/9/86 8/11-/86-e Emergency Diesel Generator System 8/16/88 9/13/86

[laciuding Fuel Oll)

{

a:

• Component Cooling Water System l 8/15/88 9/12/86 '

• Plant Air System 8/14/86 9/11/86 i

• Instrument Air System

! 8/14/86 9/11/86 i

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1 i

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V. A C. TION PLAN REPORTS, AMENDMENTS 4

& INFORMATION SUBMITTALS l 1 .

i

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( I443 )

A CTION PLAN REPORTS, AMENDMENTS, AND  :

INFORMATION SUBMITTALS Monthly Reports

• Committed in Action Plan e Content:

-Follows Organization of Action Plan  :

-Progress Report on each subject / issue '

-Appendices will contain Technical Data, Documentation

-Text will describe Findings, Actions, Results, Closures e Will continue thru Restart  :

eIntent is to Provide Information for SER as It becomes~available e Provide Results  ;

Restart Report l e Compilation of:

-Summary Report (as of 2/19/86)

-Monthly Reports

• Provide Comprehensive information for SER Preparation  ;

• Schedule, Date to be Determined

-Discussion with Staff Action Plan Amendments i e BI-Monthly, or as Needed

• Maintain Vlability of Plan l e is not expected to include results, except for Appendix B (NUREG- 1195) l -

\ .

i

3 -

8 ou2 3 A CTION PLAN -

CLOSEOUT OF OPEN ITEMS / ISSUES Definition of NRC Closecut Requirements NRR:

-Action Plan Appendix C Identifies items requiring closure

-Monthly Reports and Amendments will maintain Appendix C

-Discussion on amount of Supporting Documentation required  ;

Realon V

-Appendices to Monthly Report will contain, or reference the supporting closure documentation

-Discussion needed on what items beyond Appendix C will require submittals or NRC closecut Meetina Schedule

-Region V

-NRR ~

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-Commission I

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• Restart Schedule i

e ICS/NNI e Auxiliary Feedwater i

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( i40s )

OVERALL SCHEDULE PHILOSOPHY -

e Action Plan items -

- Scheduling of priorities ,

e Routine Activities

- CM/PM/SP

- Prioritized review of backlog

• Integrated Planning And Scheduling

- Combined engineering and site scheduling

- Centralized planning and scheduling

• Major Restart Milestones ontal m nt integ sted Leak Rate Test

- Plant Heatup / Startup

~'

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l ., A . . T PE. ,l cmo i o f,.I,,1,.I . I,21,.111l 213 18 T l, 1, i T l 8 1,81,.l . I til t.I,.I , l . lt.lr212. Tlt.I,ti,.l.Inls.I,.Itl.It.I

, , , , , , , , OVERALL RESTART SCNEDULE stort a setteur noosecoment

\

\

+ 22 Aue ne

' s oTsa ss.ovme Comosete ta sEr se e 1 zoNEE-A&3 & Doses Geneseter se sEr seMegeettee Cemeiete

! T:AIN OUTAGES A orso ssee mg Cemekte 4> o sEr se sCssN.s smere emoets a Teetme Ce=esete ,

+ s sEr as a sett.,, n.,me.m..e C.mese te i

+ i oCr se m.,s. aCs ean,A,.sgy.3,- Ioe.,, u..t o.Ee..

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, 20 oC T 36

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+

me s nov se o...,

+ u.et..ou.t.1

2. .

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ oecer nest ontese Ce<,osete E a v.., asa s. a. eat., sends., C. mar.se ZONE Z . 4>o, .T DEC ,se -

. .e,k ,e .e C..,e e .

CCOTAINhtEN T li n T

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l f,, y,*,,',C gggggpyg se g gpggy) ,

4p 24 DEC 30

___--___--___.___ 2*tetreted Leek Rete Testing (ILRT) Complete

& ET sEP 86 Non Dus Related SFAs Inspecties/Remeth Complete

& 23 sEP 86 80 Year ist ostelde Reacter Sending Complete

+ 22 sEP 80 9-236 ateheng Pump newesh/ Testing Complete

& st oCT as ZONE 3-PLANT Comosete rass wouh se Comonence/gere3se,ny ,, ,

seele Cecd Sherdown Testing CEA TUPiS TA R TUP ii JAN ST i esd Shetdown Teetine Cenertete 1 4> 14 JAN S T

' Ceneaeonce RCS Neetap l 4> 27 JAN 87 l not sherdeen Testone Cemelete 4> 28 JAN ST Begin Power Ascenalen Testing

& si FEE ST

• Power Ascenelen Testin Complete

& S T FEB T 1 Ranche sece Releeeed Te Dieretcher 1

)

_ _ _ _ _ _ . - _ - --_-___- - - - _ _. __ -. - . =. . -_ . .- -_ _-

i .

i

( 1407 )

ICS/NNI o Cabinet Wiring i

i

? - ICS 1

\

- NNI

• Modifications l -ICS

\ - NNI r

l 1

, l

• i

1 i

i s

{ 1481 )

i 4

i A UXILIA R Y FEED WA TER l

l i

l i

l

• Schedule Development l

l 4

'i l

I t

I

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. ( I488 )

SCHEDULE CONCLUSIONS  ;

• Upgrading Planning and .

Scheduling Process l

i l e Integrating Action Items I and Routine Work 1

• Ambitious / Achievable Schedule' 1

l l

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I

, e 6

I

\

CC 5

2 3

l 4

1 1

I

i,

( 400 3 1

i JUL Y 29, 198 6 COMMENTS RANCHO _SECO A CTION PLAN

\ 1.a Detailed Description Of Action items l

- System Status Report will provide details i beyond Action Plan.

1.b Specify Near-Term / Long-Term Action

- Detailed items In SSR will be prioritized

) per Action Plan Criteria.

l 1.c Definition Of Near-Term / Long-Term i - Prior to Restart -- Committee for Restart

- Near-Term -- Prior to Cycle 8 Restart  ;

l (In Cycle 7 now)- *

- Long-Term -- Prior to Cycle 9 Restart 1.d Bases For Prioritizing Near-Term / Long-Term

- Section 1.2.4 of Action Plan

- Prior to Restart: Post Trip Window / Tech Specs /

Operations Outside Control Room

- Near-Term: Enhance, Post Trip Capability /

Reliability /SS Challenges / Programmatic

- Long-Term: Support achieve ~m ent of INPO Performance Goals

e [ e4oij JUL Y 29, 1986 COMMENTS

RANCHO SECO ACTION PLAN

2. a. Schedule For Completion Of Action Plan Elements

- Expanding content of Appendix F

- Updates in Monthly Reports l

l b. Scheduling Of Evaluations, Completion Of Corrective Actions

! - Evaluations identified in Action Plan or SSR

- All recommendations will be reviewed, dispositioned, prioritized and closed per l

Q CI- 12.

i

. c. Listing Of Commitments

- To be provided In Monthly Reports

3. Cross-Referencing The Action Plan

- Amendme'nt 1 will include additional reforences to NUREG-1195 findings i -

( I402 )

JUL Y 29, 198 6 COMMENT 5 RANCHO SECO ACTION PLAN i

4. Similarities Between Action Plan And BWOG S TOP-TRIP /SPIP

- Amendment 1 will address Section 4A.3

5. Action Plan Detail On:

a. OTSG Overfill Protection

- Will expand Section 4C.3

b. Makeup /HPI System

. SSR being developed

- Will address Loss of Suction issue

c. Remote And Local Indication

- ICS/NNI SSR will resolve most questions

- SPDS & Annuciators have been evaluated by DFC

- Valve position Indication enhancements

- Human Factors enhancements

d. Containment Isolation

- SSR addressing damage to R-15001

. Reviewing response to NUREG-0 73 7, item II.E.4.2

e. Interaction Between ICS, NNI And Safety Related Systems

- SSR will address this issue.

f. Partial Loss Of ICS And NNI

- BWOG issue

- Addressed in Section 4C.1.e i -

8

( 403 )

JUL Y 29, 1986 COMMENTS RANCHO SECO ACTION PLAN

6. Reevaluation Of FSAR/USAR Accident Analysis For ICS Use

- Addressed in Action Plan Appendix B.14 Ta. Selection Of Systems For Review

- Addressed in Action Plan Section 4D.1.d

b. Similarities - Differences And Lessons Learned From Davis-Besse SRTP -

- Programmatic review

- Site visits

- Incorporation of Davis-Besse experienced staff & consultants l 8. Role Of Contractors in Rancho Seco improvement Program

- Qualifications of contracted people

- Responsibilities include hiring / training ,

of SMUD replacement

- Schedule for transition to all-SMUD organizat'on l

} -

.